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<p>Reduced activation ferritic/martensitic (RAFM) steel is regarded as one of the most promising structural materials for cladding the first wall of a fusion reactor due to its excellent overall properties. In this study, an ultrafine-grained RAFM steel was produced using a closed double equal channel angular pressing (C-DECAP) process at 600&#xa0;°C, followed by helium (He) ion irradiation at 500&#xa0;°C with an energy of 200&#xa0;keV and a fluence of 5 × 10<sup>15</sup>&#xa0;ions/cm<sup>2</sup>. The results indicate that the grain size and precipitate phases were significantly refined after deformation. Compared to the coarse-grained initial samples, the ultrafine-grained samples demonstrated superior irradiation resistance, characterized by reduced irradiation-induced hardening, a lower number density of defect clusters, smaller helium bubble sizes, and a notable decrease in dislocation loop density. Further investigation into the mechanisms underlying these improvements could facilitate the development of more resilient materials for advanced applications in nuclear environments. Additionally, irradiation-induced defects were primarily localized along martensitic lath boundaries, suggesting that grain boundaries are effective sinks for defect absorption.</p>

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Study on Irradiation Resistance of RAFM Steel Subjected to Closed Double Equal Channel Angular Pressing

  • 期刊论文

  • 发表日期：

    2026年3月21日

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  • Kemin Xue,
  • Liangwei Dai,
  • Zhipeng Chen,
  • Kecheng Wang,
  • Ping Li

摘要

Reduced activation ferritic/martensitic (RAFM) steel is regarded as one of the most promising structural materials for cladding the first wall of a fusion reactor due to its excellent overall properties. In this study, an ultrafine-grained RAFM steel was produced using a closed double equal channel angular pressing (C-DECAP) process at 600 °C, followed by helium (He) ion irradiation at 500 °C with an energy of 200 keV and a fluence of 5 × 1015 ions/cm2. The results indicate that the grain size and precipitate phases were significantly refined after deformation. Compared to the coarse-grained initial samples, the ultrafine-grained samples demonstrated superior irradiation resistance, characterized by reduced irradiation-induced hardening, a lower number density of defect clusters, smaller helium bubble sizes, and a notable decrease in dislocation loop density. Further investigation into the mechanisms underlying these improvements could facilitate the development of more resilient materials for advanced applications in nuclear environments. Additionally, irradiation-induced defects were primarily localized along martensitic lath boundaries, suggesting that grain boundaries are effective sinks for defect absorption.